Index Catalog // ScholarsArchive@OSU

Thermal hydraulic analysis of a pressurized water reactor

Creator:: Oylear, Joan Marie
Resource Type:: Masters Thesis
Full Text:: Thermal Hydraulic Analysis of a Pressurized Water Reactor

An evaluation of a neutron "flux trap" control scheme for pressurized water reactors

Creator:: Anderson, Michael Jay
Abstract:: Pressurized water reactors are presently controlled by the use of materials which absorb neutrons as their only effect; this reduces the neutron economy of the system, since these neutrons are lost without helping to maintain the chain reaction. The system examined in this study replaces these absorbing materials with a...
Resource Type:: Masters Thesis
Full Text:: pressurized water reactors AN ABSTRACT OF THE THESIS OF Michael J. Anderson for the degree of Master of

Development and implementation of an improved formulation of the momentum balance for a Once Through Steam Generator transient model

Creator:: Luo, Shyr Tung
Abstract:: A detailed formulation of the momentum equation including the Baroczy model for two phase friction is presented in this thesis. Numerical techniques for solving this equation along with the remainder of the describing equations are also presented. This model has been incorporated into an existing thermal hydraulic code for simulating...
Resource Type:: Masters Thesis
Full Text:: itself, the steam generator is one of the principal components in a pressurized water reactor (PWR

Thermal hydraulic analysis of a U-tube steam generator in a pressurized water reactor

Creator:: Chadly, Peter Brent
Abstract:: A vital safety concern in the analysis of nuclear power reactors is the thermal hydraulic behavior of the reactor coolant system under steady state and transient conditions. The goal of this study has been to develop an appropriate model for the U-tube type steam generators in a typical pressurized water...
Resource Type:: Masters Thesis
Full Text:: a pressurized water reactor AN ABSTRACT OF THE THESIS OF Peter B. Chadly for the degree of Master

The study of cold leg thermal stratification in APEX-CE

Creator:: Antoine, Stephanie Y. L. Antoine
Abstract:: This research presents an analysis of thermal stratification in the reactor cold leg of the Advanced Plant Experiment-Combustion Engineering (APEX-CE). This phenomenon may be a precursor leading to a Pressurized Thermal Shock (PTS) event in a nuclear power plant. This work was performed in support of the U.S. Nuclear Regulatory...
Resource Type:: Masters Thesis
Full Text:: Loop Water in Pressurized Water Reactor Cold Legs" [10], Sun et al. studied the phenomenon of

Oxidation of Zircaloy-4 in pressurized water reactor conditions

Creator:: VanWinkle, James A.
Abstract:: A study of the oxidation of zircaloy in reactor environments has been undertaken with the goal of characterizing of the Thermal Gradient Test Facility (TGTF) at Teledyne Wah Chang, Albany. A set of oxidation models is presented from the literature, as well as an extensive database of published oxidation test...
Resource Type:: Masters Thesis
Full Text:: Oxidation of Zircaloy-4 in pressurized water reactor

Experimental investigation of condensation phenomena inside a U-tube steam generator

Creator:: Collins, Brian A.
Abstract:: Reflux condensation tests examining steam condensation in a PWR steam generator (SG) were conducted at the Oregon State University (OSU) Advanced Plant Experiment (APEX) Test Facility from 2005 through 2007. The experimental data collected will provide a basis to assess TRACE steam generator modeling techniques and assist in development of...
Resource Type:: Masters Thesis

An analysis of core uncovery in the APEX test facility

Creator:: Rusher, Christopher deCastrique
Abstract:: The Department of Nuclear Engineering at Oregon State University has performed a series of confirmatory tests for the United States Nuclear Regulatory Commission (USNRC). These tests have been conducted in the Advanced Plant Experiment (APEX) Facility which is a one quarter height scaled simulation of the Westinghouse Advanced Passive 600...
Resource Type:: Masters Thesis
Full Text:: 600 megawatt electric (AP600) pressurized water reactor. The purpose of the testing program is to

A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility

Creator:: Wachs, Daniel M.
Abstract:: The phenomena of interest in this work is the thermal stratification which occurs during the early stages of a loss of coolant accident (LOCA) in the OSU APEX Thermal Hydraulic Test Facility, which is a scaled model of the Westinghouse AP600 nuclear power plant. Thermal stratification has been linked to...
Resource Type:: Masters Thesis
Full Text:: actuated and this isolation is broken. The high density cold water falls into the reactor. As the CMT

Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown

Creator:: Colpo, Sarah E.
Abstract:: Counter Current Flow Limitation (CCFL) was observed in the pressurizer surge line of the Oregon State University APEX facility during test NRC-10. This test simulated a one-inch diameter cold leg break with a failure of three of four of the fourth-stage Automatic Depressurization System (ADS) valves. The result was a...
Resource Type:: Masters Thesis
Full Text:: Counter Current Flow Limitation (CCFL) in the primary system of a Pressurized Water Reactor (PWR) has

ScholarsArchive@OSU

Thermal hydraulic analysis of a pressurized water reactor

An evaluation of a neutron "flux trap" control scheme for pressurized water reactors

Development and implementation of an improved formulation of the momentum balance for a Once Through Steam Generator transient model

Thermal hydraulic analysis of a U-tube steam generator in a pressurized water reactor

The study of cold leg thermal stratification in APEX-CE

Oxidation of Zircaloy-4 in pressurized water reactor conditions

Experimental investigation of condensation phenomena inside a U-tube steam generator

An analysis of core uncovery in the APEX test facility

A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility

Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown

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